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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
Sangeeta B. Kolavekar, G. B. Hiremath, N. M. Badiger, N. H. Ayachit
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1506-1519
Technical Paper | doi.org/10.1080/00295639.2022.2149232
Articles are hosted by Taylor and Francis Online.
The impact of TeO2 on the elastic and radiation shielding properties of phospho-tellurite glasses doped with varying amounts of Sm2O3 has been studied. The elastic properties, such as packing factor, packing density, Young’s modulus, bulk modulus, shear modulus, and Poisson’s ratio, were determined by using the Makashima-Mackenzie and Rocherulle models. The gamma-ray shielding parameters, such as mass attenuation coefficient, half-value layer, tenth-value layer, effective atomic number, equivalent atomic number, exposure buildup factor, and energy absorption buildup factor, were calculated using Phy-X/PSD software in the energy range from 0.015 to 15 MeV at penetration depths up to 40 mean free paths for selected glasses. The fast neutron removal cross section was also determined using Phy-X/PSD software. The results show that the mass attenuation coefficient decreases with increasing photon energy but is not influenced by the addition of Sm2O3. The exposure buildup factor values and energy absorption buildup factors have lower values in the low- and high-energy regions and higher values in the intermediate energy region. The 1.5 mol % concentration of Sm2O3 in the selected glass shows higher exposure buildup factor and energy absorption buildup factor values in the intermediate energy region. Among the selected glasses, PZBTS1.5 has the highest value of fast neutron removal cross sections. The high density, high effective atomic number, and transparency to visible light of these materials indicate that they can be used as shielding materials in nuclear reactors and nuclear technology.